JPH02306187A - Radioactive waste body inspecting equipment - Google Patents

Abstract

PURPOSE:To achieve a maintaining of a treating capacity regardless of any waste body unqualified by providing a plurality of inspecting apparatuses arranged sequentially in an inspection line, a transport means and a discriminating transport means to discriminate a waste body determined to be qualified from that determined not to be qualified. CONSTITUTION:A waste body 2 transported together with a pallet 3 by a forklift or the like is moved to a tie-in point of a waste body hoist 4 with a conveyor 1 for pallets to be transferred to a conveyor 5 for waste bodies from the pallet 3 and stopped at a specified position with respect to a rough surface dosage rate measuring device 21. The waste body 2 in which a surface dosage rate measured with the measuring device 21 is determined to be below a specified value is moved again with the conveyor 5 to be supplied to a surface pollution density/detailed surface dosage rate measuring device 22. In addition, the waste body 2 with the surface dosage rate determined to be over the specified value by the measuring device 21 is separated to a branch disposed conveyor 6 at a branch point provided in the course of the conveyor to be preserved temporarily without being supplied to the measuring device 22.

Description

DETAILED DESCRIPTION OF THE INVENTION [Industrial Application Field] The present invention relates to radioactive waste inspection equipment that performs various inspections necessary for transporting radioactive waste generated at a nuclear power plant or the like out of the facility.

[Conventional technology] Radioactive waste generated at nuclear power plants, etc. is solidified into a stable state using a solidifying agent such as cement, and then stored on the premises of each power plant. Plans are being made to remove the body from the site and centrally manage and dispose of it. In order to implement this, it is necessary to ensure that the target waste meets certain requirements for transportation and burial for disposal.

Regarding the requirements for radioactive waste solidified in 200Q drums, etc., please refer to the Prime Minister's Office Ordinance [Regulations for Burying Projects of Waste such as Nuclear Fuel Materials] and the Science and Technology Agency Notice ``Regarding Burial of Nuclear Fuel Materials, etc.'' The scope related to the burial of waste bodies is indicated in the "Notification on Borrowing, etc.", and the scope related to the transportation of waste bodies is indicated by laws and regulations such as the Nuclear Reactor AM Act and its Enforcement Order. ing.

Based on these laws and regulations, LJL rules, etc., it is considered that waste bodies transported from facilities such as nuclear power plants require inspection work to confirm that they satisfy several requirements. To give specific examples, it is considered necessary to check the following items.

(1) Waste weight (2) Surface contamination', degree (3) Surface/lrn gland mass ratio (4) Radioactivity once (5) Cement solidified body - axial compressive strength. It is stipulated that each piece of waste should be marked with an identification label.

It would take a considerable amount of time to carry out the above series of inspections for each waste body, but it is important to note that it would take a considerable amount of time to carry out the above series of inspections for each waste body. Although there are cases of blood exsanguination to some extent in each business establishment, the number of blood exsanguinations is quite large, ranging from several thousand to tens of thousands of blood vessels, so there is a need to perform efficient testing operations and improve testing processing capacity.

As a means to improve waste inspection and processing capacity.

A method of arranging a plurality of inspection devices in a series to achieve assembly-line work, or a method of performing parallel work by arranging multiple inspection devices for time-consuming inspection items, etc., are being considered.

[Published by Nikkan Kogyo Shimbun, Atomic Crab Industry 1989 (No. 35)
Volume No. 4), P, 60-64 [L11 Emission Inspection Technology for Low-Level Radioactive Waste] (Problem to be Solved by the Invention) However, some of the waste objects subject to inspection may be found to be outside the specified range. If it is assumed that the above-mentioned waste will be generated, there is a concern that if these non-standard wastes are excluded from the inspection results in the above method, the throughput of the inspection apparatus as a whole will decrease accordingly. Items that are not specified here do not necessarily mean that they are defective; for example, as the surface linearity of the waste material currently exceeds a certain standard, it is necessary to take precautions such as using a special shielding container. This term is mainly used to refer to waste materials that, after several years of continued storage, can be rationally transported due to the attenuation of radioactivity.

Assuming a case where the waste is found to be outside the regulations in the inspection items after the equipment consists of multiple inspection devices, as in the above technology, most of the inspection work and the time required for the waste will be required. As a result, the processing capacity of the inspection equipment as a whole decreases and work efficiency deteriorates.

In this way, the above technology does not take into account the issue of preventing a decline in the overall processing capacity of the inspection equipment due to the generation of unspecified waste during a series of inspection operations, and the results of the inspection are not specified. There was a problem in that as the number of waste bodies to be disposed of increased, a corresponding decrease in efficiency was unavoidable.

An object of the present invention is to provide radioactive waste inspection equipment that can be used without reducing the overall processing capacity of the inspection apparatus even if waste that does not meet the specifications is generated during the inspection.

[Means for Solving the Problems] In order to achieve the above object, the present invention provides radioactive waste inspection equipment as described in each of the claims.

[For production] In the claimed inspection equipment, a series of inspections.

By installing inspection equipment corresponding to the inspection items that are most likely to result in non-standard waste during work at the most upstream side of the inspection line, waste that is non-standard can be detected as early as possible. By immediately excluding the waste from a series of inspection processes and collecting it separately, the efficiency of the inspection equipment can be improved.

In particular, if there are many waste objects with a high surface RfA dose rate that requires compliance with transportation standards, etc., the inspection equipment installed at the most upstream side of the inspection line should be a device that roughly measures the surface dose rate of the waste objects. Therefore, it is possible to improve inspection work efficiency by sorting and excluding these items before carrying out a series of full-scale detailed inspections.

Particularly, in the configuration according to claim 3, the means for carrying out within-spec waste bodies from the inspection equipment can be used as means for carrying out non-standard waste bodies, and the equipment is simplified.

[Example] An example of the present invention will be described below with reference to FIG. 1st
The figure shows radioactive waste generated at nuclear power plants, etc.
b made by solidifying 00 in a drum.
'6 This shows the inspection items and inspection procedures for confirming the soundness of waste bodies before transporting them from facilities such as the nuclear power plant.

The waste (drum) is first subjected to an inspection using inspection equipment (ionization chamber type opener, etc.) that measures the approximate surface dose rate, and it is determined that the approximate surface dose rate of the waste is below a specified level. (Step ①) This is done from the following viewpoints. In other words, as a method for transporting waste leaves that have undergone various inspections and been confirmed to be sound, from a facility such as a nuclear power plant, it may be possible to store the waste leaves in a container that can store them in units of 8 leaves, for example. However, in order to ensure that the surface dose rate of the container is below a certain value in compliance with transportation regulations when these items are stored in a container, the surface dose rate of each waste to be stored in the container must be adjusted. It is necessary to keep it below a predetermined value in advance, and for this reason, the approximate surface weight percentage of the waste is measured at the beginning of the inspection process as described above. And this ill
Waste objects whose fixed value is below the predetermined value and which are determined to be able to be stored in the 8-wood container are subsequently subjected to the next inspection step (①) and subsequent inspection steps. On the other hand, if the surface dose rate exceeds the predetermined value, the M
6. Waste bodies for which it is judged that it is advisable to wait for the surface dose rate to decrease due to radioactivity decay of the waste bodies themselves are separated and excluded without going through the series of inspection steps shown in the next step ①.

For waste bodies that have been determined to be below the predetermined value in the above-mentioned rough surface dose rate reduction process (■) and have been submitted to the next inspection process, as a full-scale inspection to confirm their soundness,
Detailed surface dose rate (surface/1 m), surface contamination density (measured by smear method), waste weight removal, nuclide analysis (radioactivity concentration of various radioactive substances in waste), etc. will be measured. Furthermore, for radioactive waste solidified in containers (drums) using cement as the solidifying material, confirm that it has a uniaxial compression n degree of 15 kg/- or more as required by the standards. We also carry out inspections for this purpose.

In this embodiment, these tests are performed in series with the functions distributed for each test, but a method in which two or more tests are performed collectively is also conceivable.

In each of the above-mentioned inspection processes, waste objects that are determined to be non-standard in any of the inspections are not sent to the next inspection process, but are collected separately and temporarily stored. After a series of inspection operations have been completed, the temporarily stored sorted waste is palletized, distinguishing it from waste that was determined to be within specifications in all inspections.

Waste bodies that are determined to be within the specifications in all inspections are sent to the labeling process, where work such as attaching a colored band indicating the prescribed radiation dose to the waste body is carried out.

In FIG. 1, the time shown on the left side of each inspection process, labeling process, etc. indicates the time required to perform the work in each process.

FIG. 2 shows a specific example of the configuration of equipment for inspecting waste bodies as explained in FIG. 1. The inspection 81m of this embodiment will be described below with reference to this figure.

20012 A waste body 2 consisting of solid radioactive waste in a drum can is placed on a pallet 3, which is usually used for storage in a power plant, and is placed on a pallet 3 where four water wheels are arranged. The waste 2 transported with a pallet 3 by a forklift or the like (not shown) to be supplied to the inspection device is moved by a pallet conveyor 1 to the engagement position of the waste lifting device 4, and is lifted to a predetermined position by the lifting device 4. At this position, the waste 2 is transferred from the pallet 3 to the waste conveyor 5. F! 6 The waste body 2 transferred to the river bear 5 is m
It is moved by the waste conveyor 5 and stopped at a predetermined position relative to the approximate surface Ia mass rate measuring device 21. The waste body 2 whose surface jIA dose rate is measured by the rough surface dose rate measuring device 21 and determined to be below a predetermined value is moved again by the waste body conveyor 5 to the surface contamination density/detailed surface which is the primary inspection device. It is provided to the dose rate measuring device 22.

On the other hand, the waste 2 whose surface dose rate measured in the rough surface dose rate measurement 1a21 is determined to be equal to or higher than the predetermined value is not subjected to the surface contamination density/detailed surface R1A dose rate monitoring 22. At a branch point provided in the middle of the waste conveyor 5, the waste is sorted and temporarily stored on the sorted waste conveyor 6.

All the bodies 2 to be inspected are sequentially sorted by such operations according to whether the surface dose rate is above or below a predetermined value.

After the human blood 7Q staining density/detail line and the U-shaped side measuring device 22 have been inspected, the waste body 2 is transferred to the waste body conveyor 5 in a similar manner to the 5M stage, the weight measuring device 23, and the nuclide analysis device 24.
and - the axial pressure longitudinal strength regulator 25 is used to complete a series of inspection operations for confirming the integrity of the waste body 2; Thereafter, the waste body 2 is moved to the labeling device 26 by the same operation, and work such as pasting the color -1+F indication due to the serious radiation dose of J9R on the waste body 2 is performed, and all the work is completed. do. However, waste that is determined to be out of specification in any of these inspection steps will be separated as described below without undergoing the next S inspection and labeling.

The Ff6 waste 2 whose labeling work has been completed is moved by the waste lateral movement conveyor 7 from the waste conveyor 5 to the waste return conveyor 8, and is further transferred to the waste lifting device 4 by the return conveyor 8. After being moved to the matching position, the pallet return conveyor 1 is moved by the waste lifting equipment e14.
It is transferred to pallet 3 set above 0.

Here, the pallet 3 for transferring the waste 2 is used for returning the empty pallet from the pallet conveyor 1 after the waste 2 has been provided for the previous inspection work on the pallet conveyor 1. By slidingly moving to the conveyor 10, it is possible to supply just the right amount.

Although it was determined that it was out of specification in any of the inspection processes from the surface contamination density/detailed dose rate measuring device 22 to the unconfined compressive strength measuring device 25, 6 rejected bodies 2 will not be able to carry out subsequent inspections and labeling work. Instead, they are sorted onto the sorted waste conveyor 6 via the waste conveyor 5, the waste lateral movement conveyor 7, the waste return conveyor 8, and the non-standard waste conveyor 9 that branches off from the middle. Ru.

Inspection of the waste 2 sorted on the sorted waste conveyor 6 by the rough surface dose semi-open detector 21, and from the surface t/7 dye density/detailed surface dose rate meter 22 to the unconfined compressive strength determiner 25. During the process, it was determined that the conveyors 5 and 7 were out of specification.
, 8.9, and the waste is sorted on conveyor 6 for sorted waste.
After a predetermined number of waste bodies 2 that are within the specifications after a series of inspection work are collected on a pallet 3 by a waste body lifting device 4 and carried out on a pallet return conveyor 10, By operating the sorted waste conveyor 6 and the substandard waste conveyor 9 in the reverse direction of the aforementioned sorting operation, the waste is returned onto the waste return conveyor 9. Thereafter, the non-standard waste is collected onto the pallet 3 on the pallet return conveyor 10 in the same manner as the above-mentioned in-standard waste.

In order to separate and collect in-standard waste and non-standard waste by pallet, the number of waste held on each pallet (
In this embodiment, it is desirable to control the number of lines to be an integral multiple of 4 lines).

In this embodiment, a roller conveyor type such as the waste collection conveyor 5 is used as the means for moving the waste, but the moving means is not limited to the roller conveyor type, and the means for moving the waste is not limited to the roller conveyor type. It is also possible to use something like a cart with a grip.

Next, Figure 3 shows a time chart of the inspection work in the waste body inspection equipment using the information system shown in Figure 2.
The waste bodies (drums) indicated by ■, 轡, ■, etc. in the figure are subjected to a series of inspections and operations from &1 to 6, but exceed a predetermined value in the 4111+18 surface linearity test of black soil. Waste bodies determined to have a mm ratio of Approximate surface dose rate measurement is performed for one W6'9V: Since the time required to inspect one body per body is shorter than the inspection time that is rate-limiting in the following inspection process, it is assumed that two or three samples in a row are judged to have a non-standard surface dose rate. Even if there is waste, it can be absorbed during idle time, and therefore the throughput of the entire inspection device can be maintained without deteriorating.

[Effects of the Invention] According to the present invention, it is possible to detect non-standard waste as early as possible in a series of inspection processes and to separate and collect the waste, so that it is possible to detect At non-standard waste in the waste carried into the inspection facility. Even in a situation where a considerable number of waste bodies are mixed, the processing capacity of the waste body inspection equipment will not be reduced.
This makes it possible to ensure maximum efficiency. Furthermore, it is possible to transport the non-standard waste collected separately to the outside of the inspection platform using the transportation means for transporting the within-standard waste.

Equipment can be simplified.

[Brief explanation of the drawing]

FIG. 1 is an inspection flow according to an embodiment of the present invention, FIG. 2 is a perspective view of the inspection equipment, and FIG. 3 is a time chart of inspection work. 1... Conveyor for pallet transfer 2... Waste body 3... Pallet 4... Waste body lifting device 5... Conveyor for waste body transfer 6... Conveyor for separated waste body 7... Waste body lateral movement conveyor 8...Waste body return conveyor 9...Substandard waste body conveyor 10...Pallet return conveyor 21...Approximate surface dose rate measuring device 22...Surface contamination density/ Detailed surface dose rate measuring device 231
01 Weight measuring device 24... Nuclide analysis measuring device 25.
... - Axial compressive strength measuring device 26 ... Labeling device Fig. 1

Claims (1)

[Scope of Claims] 1. A radioactive waste inspection facility that performs necessary inspections on waste formed by immobilizing radioactive waste in containers such as drums in order to transport this waste outside of a storage facility. , a plurality of inspection devices arranged in sequence on an inspection line, transportation means for sequentially transporting waste between these inspection devices, and non-standard disposal determined to be non-standard in at least one inspection device. The equipment is equipped with separate transport means for collecting the waste separately from the waste that is determined to be within the specifications by all inspection equipment, and the inspection items that are most likely to determine that the waste is not within the regulations are provided. A radioactive waste inspection facility characterized by having inspection equipment equivalent to the above installed at the most upstream side of the inspection line. 2. The radioactive waste inspection equipment according to claim 1, wherein the inspection equipment installed at the most upstream side of the inspection line is a device that measures the surface dose rate of the waste in advance. 3. All inspection equipment is equipped with a transport means for transporting the non-standard waste that has been determined to be within the regulations from the inspection line to outside the inspection facility, and the said sorting transport means is used to transport the non-standard waste that has been separately collected. 2. The method of claim 1, wherein after a waste object that is determined to be within regulations in all of the inspection equipment is carried out of the inspection facility by the carry-out transport means, it can be transferred to the carry-out transport means. Radioactive waste inspection equipment described in 2.